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Compliance Assessments of Hypothetical Geological Nuclear Waste Isolation Systems with the Draft Epa Standard

Published online by Cambridge University Press:  21 February 2011

M. D. Siegel
Affiliation:
Fuel Cycle Risk Analysis Division, Sandia National Laboratories, Albuquerque, NM, 87185
M. S. Chu
Affiliation:
Fuel Cycle Risk Analysis Division, Sandia National Laboratories, Albuquerque, NM, 87185
R. E. Pepping
Affiliation:
Fuel Cycle Risk Analysis Division, Sandia National Laboratories, Albuquerque, NM, 87185
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Estimates of potential radionuclide releases from HLW storage facilities in geologic formations are an integral part of the technical basis for the regulation of nuclear waste disposal. We have attempted to assess the importance of the variation of several variables and model assumptions to the calculation of radionuclide discharge from hypothetical repositories. The conceptual models of the repository sites are consistent with our current understanding of the characteristics of the geologic environments being studied by the Department of Energy. It must be stressed that we have not attempted to accurately model any real sites; at the present time, the available data are not sufficient for this purpose. Large uncertainties exist in the characterization of the solubilities and sorption of radionuclides, in the description of the regional and local hydrogeology and in the mathematical treatment of contaminant transport in the presence of fracture flow and matrix diffusion. The fraction of waste that could be accessed by breaching the repository, the effects of mixing processes within the facility and the probability of human intrusion are not known. We have completed preliminary calculations of potential radionuclide discharges from hypothetical repositories in tuff and bedded salt [1,2]. Our theoretical approach and computational methods are illustrated in this paper with examples for a repository in volcanic tuff. We also briefly discuss the importance of radionuclide source term assumptions to the calculations for a bedded salt repository.

Type
Research Article
Copyright
Copyright © Materials Research Society 1983

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References

REFERENCES

1. Siegel, M. D. and M. S., Chu, Technical Assistance for Regulatory Development: A Simplified Repository Analysis in a Reference Tuff Site, SAND82–1741, Sandia National Laboratories, Albuquerque, NM, 1982.Google Scholar
2. Pepping, R. E., Chu, M. S., and M. D., Siegel, Technical Assistance for Regulatory Development: A Simplified Repository Analysis in a Hypothetical Bedded Salt Formation, SAND82–0996, Sandia National Laboratories, Albuquerque, NM, 1982.Google Scholar
3. Environmental Protection Agency, 40CFR191, Internal Working Draft 19, Federal Register, March 19, 1981.Google Scholar
4. Guzowski, R. V., Nimick, F. B., Siegel, M. D. and Finley, N. C., Repository Site Definition in Tuff: Yucca Mountain, Nevada, SAND82–2105, Sandia National Laboratories, Albuquerque, NM, in preparation.Google Scholar
5. Guzowski, R. V., Nimick, F. B., and Muller, A. B., Repository Site Definition in Basalt: Pasco Basin, Washington, SAND81–2088, NUREG/CR-2352, Sandia National Laboratories, Albuquerque, NM, March 1982.Google Scholar
6. Erickson, K. L., Approximations For Adapting Porous Media Radionuclides Transport Models to Analysis of Transport in Jointed Porous Rocks, in Scientific Basis for Nuclear Waste Management, Vol. 6, Brookins, D., Ed. (North-Holland, New York, 1983).Google Scholar
7. Campbell, J. E., Longsine, D. E. and Cranwell, R. M., Risk Methodology for Geologic Disposal of Radioactive Waste: The NWFT/DVM Computer Code Users Manual, SAND81–0886, Sandia National Laboratories, Albuquerque, NM, November 1981.Google Scholar
8. Iman, R. L., Davenport, J. M. and Zeigler, D. M., Latin Hypercube Sampling (Program User's Guide), SAND79–1473, Sandia National Laboratories, Albuquerque, NM, January 1980.Google Scholar
9. Cranwell, R. M. et al. , Risk Methodology for Geologic Disposal of Radioactive Waste: Final Report, SAND81–2573, NUREG/CR-2452, Sandia National Laboratories, Albuquerque, NM, to be published.Google Scholar
10. Muller, A. B., Finley, N. C., and Pearson, F. Jr., Geochemical Parameters Used in the Bedded Salt Reference Repository Risk Assessment Methodology, SAND81–0557, NUREG/CR-1996, Sandia National Laboratories, Albuquerque, NM, September 1981.Google Scholar